Browse wiki

CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE  and UTILITY TO NRC

Boron +, Copper +, Oxygen +, Hydrogen +  and Lead +

10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.44 +, 10 CFR 50 Appendix G +, 10 CFR 50.54#f +  and 10 CFR 50.44#a +

05000000  +, 05000213  +, 05000245  +, 00213  +  and 00245  +

Opeka J +, NORTHEAST UTILITIES +, Counsil W +, CONNECTICUT YANKEE ATOMIC POWER CO. +  and Northeast Nuclear Energy +

NRC Generic Letter 82-09, Environmental Qualification of Safety Related Electrical Equipment +  and NRC Generic Letter 81-04, Emergency Procedures And Training for Station Blackout Events +

A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +, A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +  and A02629, Forwards Summary of NRC Positions on 26 Unresolved Safety Issues,Consisting of Excerpts from NRC Publications & Repts to Congress & Assessment of Generic Applicability.Adequate Basis Exists to Warrant Continued Plant Operation +

Westinghouse +  and General Electric +

NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +  and NRC Bulletin 79-27 +

NUREG-0623 +, NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, NUREG-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +, NUREG-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG-0645, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG-0577, Forwards Request for Addl Info Re Low Fracture Toughness Since Facility Has Been Classified as Group 1 According to NUREG-0577.Response Should Be Submitted within 30 Days of Receipt of Ltr.Further NRC Evaluation Will Be Required +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

Regulatory Guide 1.82 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.79 +

NEDE-21821 +  and NEDO-10ll5 +

Millstone +, Haddam Neck +  and 05000000 +

Connecticut +, Maryland +  and Washington +

Steam Generator +, Reactor Coolant System +, Feedwater +, High Pressure Coolant Injection +, Reactor Protection System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Shutdown Cooling +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Automatic Depressurization System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +  and Control Rod +

TS-4.6.B +  and TS-3.4 +

Crutchfield D +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, High winds +, Reactor Vessel Water Level +, Anticipated operational occurrence +, Hydrostatic +, Nondestructive Examination +, High Energy Line Break +, Scram Discharge Volume +, Control of Heavy Loads +  and Water hammer +